REVIEW OF THE BELGIAN EXPERIENCE OF REACTOR CORE INTERNAL COMPONENTS

被引：0
|
作者：
BRIEGLEB, P
MIGNOT, P
机构：
[1] AIB-Vinçotte, 1060 Brussels, Avenue du Roi
来源：
NUCLEAR ENGINEERING AND DESIGN | 1992年 / 133卷 / 01期
关键词：
D O I：
10.1016/0029-5493(92)90087-C
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
In Belgium, some typical reactor core internal components have experienced various types of damage, which are attributed to either intergranular stress corrosion cracking (IGSCC) or to flow-induced vibrations. This paper reviews the degradation processes affecting: - control rod guide tube support pins, - rod cluster control assembly rodlets - in-core instrumentation thimbles. The investigations performed are summarized, as well as the corrective actions taken. Finally, potential safety concerns are identified.
引用
收藏
页码：41 / 47
页数：7
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